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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000285/LER-1999-002, :on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With1999-07-0808 July 1999
- on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With
05000285/LER-1999-001, :on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With1999-03-0505 March 1999
- on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With
05000285/LER-1998-006, :on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With1999-01-28028 January 1999
- on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With
05000285/LER-1998-016, :on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With1999-01-0404 January 1999
- on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With
05000285/LER-1998-015, :on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With1999-01-0404 January 1999
- on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With
05000285/LER-1998-014, :on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With1998-11-20020 November 1998
- on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With
05000285/LER-1998-012, :on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With1998-11-10010 November 1998
- on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With
05000285/LER-1998-013, :on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With1998-10-26026 October 1998
- on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With
05000285/LER-1998-009, :on 980722,waste Disposal Sys CIV Was Noted Outside Design Basis.Caused by Over Reliance on Contractor Design & Review of Mods.Mods Were Completed to Correct Problem.With1998-09-30030 September 1998
- on 980722,waste Disposal Sys CIV Was Noted Outside Design Basis.Caused by Over Reliance on Contractor Design & Review of Mods.Mods Were Completed to Correct Problem.With
05000285/LER-1998-011, :on 980825,violation of TS on Engineered Safety Sys Equipment Operability Occurred.Caused by Lack of Understanding of All Starting Air Circuit Details.Replaced Caution Tags on DG & Control Panels.With1998-09-24024 September 1998
- on 980825,violation of TS on Engineered Safety Sys Equipment Operability Occurred.Caused by Lack of Understanding of All Starting Air Circuit Details.Replaced Caution Tags on DG & Control Panels.With
05000285/LER-1998-010, :on 930208,violation of TS Re Better Axial Shape Selection Sys Was Noted.Caused by Inoperability of Core Monitoring Program.Alternate Methods Will Be Evaluated. with1998-09-17017 September 1998
- on 930208,violation of TS Re Better Axial Shape Selection Sys Was Noted.Caused by Inoperability of Core Monitoring Program.Alternate Methods Will Be Evaluated. with
05000285/LER-1998-008, :on 980528,noted That Plant Had Operated Outside of Design Basis of AFW Sys Due to Overpressurization of AFW Piping.Caused by Misadjustment of Governor.Installed Mod to Sense Overpressure Condition1998-06-29029 June 1998
- on 980528,noted That Plant Had Operated Outside of Design Basis of AFW Sys Due to Overpressurization of AFW Piping.Caused by Misadjustment of Governor.Installed Mod to Sense Overpressure Condition
05000285/LER-1998-007, :on 980522,TS Violation of ISI Reporting Requirements,Was Noted.Caused by Interpretation of Requirements of 10CFR50.55a(g)(5)(iv) Which Differs from Nrc.Listing of Exams Given to NRC1998-06-22022 June 1998
- on 980522,TS Violation of ISI Reporting Requirements,Was Noted.Caused by Interpretation of Requirements of 10CFR50.55a(g)(5)(iv) Which Differs from Nrc.Listing of Exams Given to NRC
05000285/LER-1998-005, :on 980520,161 Kv Transmission Line Circuit Breakers Tripped.Caused by Inappropriate Actuation of Deluge Sys for Transformer T1A-3.Transformer T1A-3 Was Checked to Ensure No Damage to Transformer Occurred1998-06-19019 June 1998
- on 980520,161 Kv Transmission Line Circuit Breakers Tripped.Caused by Inappropriate Actuation of Deluge Sys for Transformer T1A-3.Transformer T1A-3 Was Checked to Ensure No Damage to Transformer Occurred
05000285/LER-1998-004, :on 980423,determined That Indication in Fort Calhoun Station SG Tube Had Been Identified During 1996 Exams,But Had Been Inadvertently Left in Svc.Caused by Personnel Error.Procedures Revised1998-05-22022 May 1998
- on 980423,determined That Indication in Fort Calhoun Station SG Tube Had Been Identified During 1996 Exams,But Had Been Inadvertently Left in Svc.Caused by Personnel Error.Procedures Revised
05000285/LER-1998-003, :on 980407,violation of TS for Control of High Radiation Area Was Noted.Caused by Inadequate Communication of Mgt Expectations.Expectations of Radiation Area Controls Will Be Given to All Radiation Workers1998-05-0707 May 1998
- on 980407,violation of TS for Control of High Radiation Area Was Noted.Caused by Inadequate Communication of Mgt Expectations.Expectations of Radiation Area Controls Will Be Given to All Radiation Workers
05000285/LER-1998-002, :on 980226,TS Violation Was Noted Due to Exceeding Qualified Life for Plant Components.Caused by Lack of Depth Analysis When Original Calculation Was Performed. a Panel Was Repaired & Returned to Service1998-03-27027 March 1998
- on 980226,TS Violation Was Noted Due to Exceeding Qualified Life for Plant Components.Caused by Lack of Depth Analysis When Original Calculation Was Performed. a Panel Was Repaired & Returned to Service
05000285/LER-1997-017, :on 971107,low Pressure Safety Injection in Unanalyzed Condition Occurred,Due to Potential for Voiding. OPPD Has Administrative Controls in Place to Monitor & Prevent Conditions Necessary for Voiding1998-03-20020 March 1998
- on 971107,low Pressure Safety Injection in Unanalyzed Condition Occurred,Due to Potential for Voiding. OPPD Has Administrative Controls in Place to Monitor & Prevent Conditions Necessary for Voiding
05000285/LER-1998-001, :on 980202,TS Violation Occurred Due to Inadequate Inservice Testing.Caused by Lack of Attention to Detail When FCS ISI Program Plan for 3rd ten-year Interval Was Put Together in 1992.Changes Will Be Made1998-03-0303 March 1998
- on 980202,TS Violation Occurred Due to Inadequate Inservice Testing.Caused by Lack of Attention to Detail When FCS ISI Program Plan for 3rd ten-year Interval Was Put Together in 1992.Changes Will Be Made
05000285/LER-1997-017, :on 971107,LPSI Was in Unanalyzed Condition Due to Potential for Voiding.Caused by Architects Failure to Consider Water Hammer in Designs.Administrative Controls Placed to Monitor & Prevent Conditions1997-12-0808 December 1997
- on 971107,LPSI Was in Unanalyzed Condition Due to Potential for Voiding.Caused by Architects Failure to Consider Water Hammer in Designs.Administrative Controls Placed to Monitor & Prevent Conditions
05000285/LER-1997-016, :on 971029,nuclear Fuel Was Potentially Outside of Mfgs Fuel Design Criteria.Caused by Fuel Clad Gap Reopening.Gap Reopening May Be Predicted for Fcs,Based on Bounding Analysis1997-11-26026 November 1997
- on 971029,nuclear Fuel Was Potentially Outside of Mfgs Fuel Design Criteria.Caused by Fuel Clad Gap Reopening.Gap Reopening May Be Predicted for Fcs,Based on Bounding Analysis
05000285/LER-1997-015, :on 971017,unanalyzed Condition for Station Batteries Was Noted.Caused by Lack of Detailed Plant Design to Provide Supporting Info Re Requirement.Issued Operations Memo1997-11-17017 November 1997
- on 971017,unanalyzed Condition for Station Batteries Was Noted.Caused by Lack of Detailed Plant Design to Provide Supporting Info Re Requirement.Issued Operations Memo
05000285/LER-1997-014, :on 970831,perimeter Microwave Intrusion Alarm on Zone 2 Received in Security Alarm Stations.Caused by Lack of Attention to Detail on Behalf of CAS & SAS Operators. Alarm Station Operators Involved Retrained1997-09-26026 September 1997
- on 970831,perimeter Microwave Intrusion Alarm on Zone 2 Received in Security Alarm Stations.Caused by Lack of Attention to Detail on Behalf of CAS & SAS Operators. Alarm Station Operators Involved Retrained
05000285/LER-1997-013, :on 970826,TS 2.0.1, Motherhood Was Entered Into General Shutdown Voluntarily.Caused by Failed Switch. Replaced & Tested Inverter Switch & Returned Plant to Full Power1997-09-25025 September 1997
- on 970826,TS 2.0.1, Motherhood Was Entered Into General Shutdown Voluntarily.Caused by Failed Switch. Replaced & Tested Inverter Switch & Returned Plant to Full Power
05000285/LER-1997-012, :on 970821,inadvertent Isolation of All Containment Spray Was Discovered.Caused by Operator Error. Operator,Shift Supervisors,Licensed Senior Operators & Licensed Operators Were Disciplined1997-09-22022 September 1997
- on 970821,inadvertent Isolation of All Containment Spray Was Discovered.Caused by Operator Error. Operator,Shift Supervisors,Licensed Senior Operators & Licensed Operators Were Disciplined
05000285/LER-1997-011-01, :on 970819,violation of Tech Specs Due to Inoperability of Radiation Monitor Occurred.Caused by Lack of Depth in Evaluation/Review by Station Personnel. Procedures Will Be Revised1997-09-19019 September 1997
- on 970819,violation of Tech Specs Due to Inoperability of Radiation Monitor Occurred.Caused by Lack of Depth in Evaluation/Review by Station Personnel. Procedures Will Be Revised
05000285/LER-1997-010, :on 970731,violation of TS Occurred While Moving Spent Fuel in Spent Fuel Pool.Caused by Inadequate Design of CEA Locking Clip.Moved Affected Assembly to Region I of Spent Fuel Pool1997-09-0202 September 1997
- on 970731,violation of TS Occurred While Moving Spent Fuel in Spent Fuel Pool.Caused by Inadequate Design of CEA Locking Clip.Moved Affected Assembly to Region I of Spent Fuel Pool
05000285/LER-1997-004, :on 970505,DG Was Outside Design Basis Due to Violation of App R.Mod Was Completed on 970507 to Provide Ability to Isolate CR Located Tachometer from DG-2 Speed Sensing Circuit Prior to Reaching 300 Degrees1997-08-13013 August 1997
- on 970505,DG Was Outside Design Basis Due to Violation of App R.Mod Was Completed on 970507 to Provide Ability to Isolate CR Located Tachometer from DG-2 Speed Sensing Circuit Prior to Reaching 300 Degrees
05000285/LER-1997-008, :on 970616,improper Shift Staffing Due to Inadequate Control of Respirator Spectacle Kits Occurred. Caused by Program for Obtaining Corrective Lenses Inadequate to Ensure Compliance w/10CFR.Manual Revised1997-07-16016 July 1997
- on 970616,improper Shift Staffing Due to Inadequate Control of Respirator Spectacle Kits Occurred. Caused by Program for Obtaining Corrective Lenses Inadequate to Ensure Compliance w/10CFR.Manual Revised
05000285/LER-1997-009, :on 970619,potential Loss of Remote Shutdown Capability Occurred Due to Fire Induced Damage.Caused by Inadequate Design Basis Documentation.Operations Memo Provided Evacuation Criteria1997-07-12012 July 1997
- on 970619,potential Loss of Remote Shutdown Capability Occurred Due to Fire Induced Damage.Caused by Inadequate Design Basis Documentation.Operations Memo Provided Evacuation Criteria
05000285/LER-1997-006, :on 970606,discovered Loss of All Fire Suppression Due to Inoperability of Fire Pumps.Caused by Atypical Set of Operating Circumstances.Procedures Are Being Modified to Prevent Recurrence of Event1997-07-0707 July 1997
- on 970606,discovered Loss of All Fire Suppression Due to Inoperability of Fire Pumps.Caused by Atypical Set of Operating Circumstances.Procedures Are Being Modified to Prevent Recurrence of Event
05000285/LER-1997-005, :on 970530,improper Entry Into High Radiation Area Occurred.Caused by Lack of self-checking & Inattention to Detail.Discussed Event W/Plant Staff & Counseled Individual Involved1997-06-27027 June 1997
- on 970530,improper Entry Into High Radiation Area Occurred.Caused by Lack of self-checking & Inattention to Detail.Discussed Event W/Plant Staff & Counseled Individual Involved
05000285/LER-1997-002, :on 970414,charging Pump CH-1B Declared Inoperable.Caused by Ineffective Communication Re Amend 125 to TS 2.15.Implemented Improved Procedures Re Submittal of License Amend Requests1997-05-14014 May 1997
- on 970414,charging Pump CH-1B Declared Inoperable.Caused by Ineffective Communication Re Amend 125 to TS 2.15.Implemented Improved Procedures Re Submittal of License Amend Requests
05000285/LER-1997-001, :on 970122,main Steam Outside of Design Basis Occurred Due to an Error in Safety Valve Analysis.Guidance Has Been Provided to Operating Staff to Ensure That Design Basis Maintained1997-02-21021 February 1997
- on 970122,main Steam Outside of Design Basis Occurred Due to an Error in Safety Valve Analysis.Guidance Has Been Provided to Operating Staff to Ensure That Design Basis Maintained
05000285/LER-1996-015, :on 961028,improper Fuel Loading Next to Inoperable Wide Range Nuclear Instrument Occurred.Caused by Inadequate procedures.OP-11 Will Be Revised Before 1998 Refueling Outage to Require Reloading1997-01-21021 January 1997
- on 961028,improper Fuel Loading Next to Inoperable Wide Range Nuclear Instrument Occurred.Caused by Inadequate procedures.OP-11 Will Be Revised Before 1998 Refueling Outage to Require Reloading
05000285/LER-1996-016, :on 961220,inadequate Procedural Guidance for Resetting an Engineering Safety Feature Identified.Caused by Lack of Depth in Evaluation.Memorandum Was Issued to Notify Operators of Issue1997-01-21021 January 1997
- on 961220,inadequate Procedural Guidance for Resetting an Engineering Safety Feature Identified.Caused by Lack of Depth in Evaluation.Memorandum Was Issued to Notify Operators of Issue
05000285/LER-1996-014, :on 961117,reactor Cooldown in Excess of Limits Occurred Due to Starting Reactor Coolant pumps.OP-2A & OI-RC-9 Will Be Revised1996-12-17017 December 1996
- on 961117,reactor Cooldown in Excess of Limits Occurred Due to Starting Reactor Coolant pumps.OP-2A & OI-RC-9 Will Be Revised
05000285/LER-1996-013, :on 961116,util Failed to Satisfy Surveillance Requirement for Containment Penetration M-80.Caused by Lack of Complete & Thorough Ca.Review of All Similarly Configured Penetrations Was Conducted1996-12-13013 December 1996
- on 961116,util Failed to Satisfy Surveillance Requirement for Containment Penetration M-80.Caused by Lack of Complete & Thorough Ca.Review of All Similarly Configured Penetrations Was Conducted
05000285/LER-1996-012, :on 961111,potential for Vaporizing Cooling Water in Containment Fan Cooling Units Occurred.Caused by Loop Coincident with Loca.Analyses Have Been Performed1996-12-11011 December 1996
- on 961111,potential for Vaporizing Cooling Water in Containment Fan Cooling Units Occurred.Caused by Loop Coincident with Loca.Analyses Have Been Performed
05000285/LER-1996-011, :on 961030,containment Closure Breached While Moving Fuel.Caused by Failure to Maintain Valves & Follow & Enforce SO-G-20A Requirements.Rev of Policies & Procedures Re Control & Maint of Containment Closure1996-11-27027 November 1996
- on 961030,containment Closure Breached While Moving Fuel.Caused by Failure to Maintain Valves & Follow & Enforce SO-G-20A Requirements.Rev of Policies & Procedures Re Control & Maint of Containment Closure
05000285/LER-1996-010, :on 961018,loss of Containment Closure Noted Due to Maint Activity During Refueling.Station Procedures Including OI-CO-4,will Be Reviewed & Revised as Necessary to Ensure Adequate Controls Exist1996-11-18018 November 1996
- on 961018,loss of Containment Closure Noted Due to Maint Activity During Refueling.Station Procedures Including OI-CO-4,will Be Reviewed & Revised as Necessary to Ensure Adequate Controls Exist
05000285/LER-1996-009, :on 961017,pressurizer Safety Valves as Found Lift Appeared to Be Outside Acceptance Criteria.Caused by Valve Bonnet Upper Temp Limits Not Specified in Test Procedure.Test Procedure Will Be Revised1996-11-18018 November 1996
- on 961017,pressurizer Safety Valves as Found Lift Appeared to Be Outside Acceptance Criteria.Caused by Valve Bonnet Upper Temp Limits Not Specified in Test Procedure.Test Procedure Will Be Revised
05000282/LER-1996-018, :on 961010,surveillance of Low Pressure Start of Component Cooling Pumps Was Missed Due to Inadequate Procedure.Procedures Will Be Revised by 970215 to Test Low Pressure auto-start of Component Cooling Pumps1996-11-12012 November 1996
- on 961010,surveillance of Low Pressure Start of Component Cooling Pumps Was Missed Due to Inadequate Procedure.Procedures Will Be Revised by 970215 to Test Low Pressure auto-start of Component Cooling Pumps
05000285/LER-1996-008, :on 961011,ventilation Isolation Actuation Signal Occurred.Due to High Containment Activity.Plant Procedures Will Be Reviewed & Revised1996-11-12012 November 1996
- on 961011,ventilation Isolation Actuation Signal Occurred.Due to High Containment Activity.Plant Procedures Will Be Reviewed & Revised
05000285/LER-1996-007, :on 961005,unplanned Reactor Protection Sys Actuation Occurred During Plant Cooldown.Caused by Failure to Complete Step in OP-3A as Required.Procedure Revised.W/1996-11-0404 November 1996
- on 961005,unplanned Reactor Protection Sys Actuation Occurred During Plant Cooldown.Caused by Failure to Complete Step in OP-3A as Required.Procedure Revised.W/
05000285/LER-1996-006, :on 951218,all Charging Pumps Disabled.Caused by Inadequate Administrative Control.Guidance Insuring Consistent Interpretation of Affected TSs Issued.Process for Issuing TS Interpretations Revised1996-10-0909 October 1996
- on 951218,all Charging Pumps Disabled.Caused by Inadequate Administrative Control.Guidance Insuring Consistent Interpretation of Affected TSs Issued.Process for Issuing TS Interpretations Revised
05000285/LER-1996-004, :on 960315,discovered Adequate Shutdown Margin Was Not Maintained.Caused by Inadequate Technical Review by Plant Personnel Involved in Reviewing Procedure Change. Appropriate Personnel Trained on Incident1996-06-0303 June 1996
- on 960315,discovered Adequate Shutdown Margin Was Not Maintained.Caused by Inadequate Technical Review by Plant Personnel Involved in Reviewing Procedure Change. Appropriate Personnel Trained on Incident
05000285/LER-1996-002, :on 960329,reactor Manually Tripped Due to Partial Loss of Vacuum in Main Condenser.Condenser Isolated, Plant Shutdown & Leaking Condenser Tube Plugged.Pm Order WP-006820 Will Be Revised1996-04-29029 April 1996
- on 960329,reactor Manually Tripped Due to Partial Loss of Vacuum in Main Condenser.Condenser Isolated, Plant Shutdown & Leaking Condenser Tube Plugged.Pm Order WP-006820 Will Be Revised
05000285/LER-1996-001, :on 960318,containment Ventilation Isolation Signal Occurred Due to High Activity During Purge.Revised Applicable Procedures1996-04-17017 April 1996
- on 960318,containment Ventilation Isolation Signal Occurred Due to High Activity During Purge.Revised Applicable Procedures
05000285/LER-1995-007, :on 951108,potential Tripping of 480 Volt Circuit Breakers W/Digital Reip Units Identified.Caused by Circuit Breaker Component Not Operating as Specified.Issued SA for Operability1996-03-0404 March 1996
- on 951108,potential Tripping of 480 Volt Circuit Breakers W/Digital Reip Units Identified.Caused by Circuit Breaker Component Not Operating as Specified.Issued SA for Operability
1999-07-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 05000285/LER-1999-002, :on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With1999-07-0808 July 1999
- on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With
LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 05000285/LER-1999-001, :on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With1999-03-0505 March 1999
- on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With
LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 05000285/LER-1998-006, :on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With1999-01-28028 January 1999
- on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With
05000285/LER-1998-016, :on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With1999-01-0404 January 1999
- on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With
05000285/LER-1998-015, :on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With1999-01-0404 January 1999
- on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With
LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated 05000285/LER-1998-014, :on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With1998-11-20020 November 1998
- on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With
ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion 05000285/LER-1998-012, :on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With1998-11-10010 November 1998
- on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With
LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 05000285/LER-1998-013, :on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With1998-10-26026 October 1998
- on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With
1999-09-30
[Table view] |
text
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Omaha Public Power District P.O. Box 399 Hwy.75 - North of Pt. Calhoun Fort Calhoun. NE 680234399 -
402/636-2000 February 9, 1990 LIC-90-0106 U. S. Nuclear Regulatory Commission Attn: Document Control Desk R
L Mail Station P1-137
- ~
Washington,_DC 20555 References-Docket No. 50-285 Gentlemen:
[
Subject: Licensee Event Report 90-01 for the Fort Calhoun Station L
L' Please find attached Licensee Event Report-90-01 dated February 9, 1990.
This report'is being submitted per requirements of 10 CFR
'50.73(a)(2)(i)(B).
L If you should have any questions, please contact me, l
Sincerely, l
A0 0 M W. G, Gates-Division Manager l,
- - Nuclear Operations-(
4 WGG/ tem ~
Attachment c:
R. D. Marti*
NRC Regional Administrator A.~Bournia, RC Project Manager P. H. Harrell, NRC Senior Resident Inspector A
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' Fort Calhoun Station Unit No. 1 0151010101218 15 1 loFl 013 TITLt 14)
Failure to Imolement' Fire Watch Patrol
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NiME TELEPHONE NUMetR ARtaCoot Larry L. Lehman, Shif t Technical Advisor 41012 513111 16 I RI? lo COMPLITE ONE LINE FOR B ACH COMPONENT f AILumt otacMietD IN TMit REPORT 1131 R{0 I
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e, n.1 A Fire Barrier Breach Permit for the wall between Auxiliary Building Rooms 26 and 34 was taken to the Shift Supervisor for authorization on January 8, 1990.
The Shift Supervisor authorized the fire barrier breach at 1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br />, but Security was not notified to establish an hourly fire watch patrol.
Hence,.
TechnicalSpecification2.19(7)wasviolatedbyfailuretoestablishanhourly fire watch patrol for that area following the breach of the fire barrier. A separate fire watch patrol was established.in the same area on January 9, 1990 l
at 0940. The Fire Protection System Engineer discovered the discrepancy on-January 10, 1990 and initiated the required fire watch patrol.
The primary cause of this event was failure of the Shift Supervisor to assure
{
his procedural responsibility for initiating a fire watch patrol was met.
Contributin factors were past practices and inadequate training associated with the Sh ft Supervisor responsibilities of the Fire Protection Program.
Changes to the Fire Protection Program to better define associated responsibilities will be implemented by February 16, 1990. The Shift Supervisors and other licensed operators will be trained concerning each of these changes prior to implementation.
NRC Penn 300 (649)
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LER NUMSG A ($1 PA04 (31 YeIn Ew*aN Fort Calhoun Station Unit No. 1 0 15l010101 21815 91 0 01 d 1 010 01 2 oF 0 13 TEXT, mese ausse a mouse ( esas assmenew 44C Arm Mai(U)
On January 8, 1990 Fort Calhoun-Station Unit No. I was operating in Mode 1 at 100 percent power..An addition to the Auxiliary Building was under construction. The construction modification package required that a hole be bored in the fire wall between Rooms 26 and 34 of the existing building to run conduit for the new expansion. Craft personnel initiated a Fire Barrier Breach Permit form to obtain authorization to breach the fire barrier pursuant to Standing Order G-58, Control of. Fire Protection System Impairments.
The form was taken directly to the Shift Supervisor who gave authorization,to breach the fire barrier at 1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br /> on January 8, 1990.
l The Shift Supervisor assumed that the Fire Protection System Engineer had been notified and would notify Security of the need for an hourly fire watch i-patrol.
Standing Order G-58 required the Shift Supervisor or his designee to assure adequate compensatory actions were implemented prior to breaching a fire barrier.
There was no requirement for the Fire Protection System Engineer to i
be notified.
In most )revious cases the Fire Protection System Engineer had, i
when notified, taken tte actions needed to implement compensatory actions.
In this case, the craftsman did not contact the system engineer and no hourly fire watch patrol was initiated. The craftsman believed the paperwork to be in order and proceeded with breaching the fire barrier soon after authorization.
Fort Calhoun Technical Specification 2.19(7) requires that within one hour of the discovery of a degraded fire barrier, the fire-detector on at least one side of.the penetration must be verified as-operable and an hourly fire watch patrol must be established. There was no indicated inoperability of fire detectors in the affected area during this time period. Since the hourly fire watch patrol was not established, Technical Specifications were violated after the fire barrier was breached.
On January 9, 1990, at 0940, the requirement for an hourly fire watch patrol was technically met when an hourly fire watch patrol was established for l
another degraded fire barrier in the area. On January 10, 1990 the Fire Protection System Engineer discovered the missed fire watch during a review of the hourly fire watch patrol log and the fire protection impairment log.
The System Engineer notified Security and initiated the appropriate hourly fire watch patrol for the degraded fire barrier in question.
The primary cause of this event was the failure of the Shift Su)ervisor to assure his procedural responsibility for initiating a fire watc1 patrol was met.
There were several factors which contributed to this failure.
Past practice had been for the Fire Protection System Engineer to frequently assume this responsibility to reduce the work load for the Shift Supervisor; however, there was no formalized, consistent method for this delegation of responsibility.
There was also a lack of sufficient training for the Shift Supervisors on details of their responsibilities relative to processing of Fire Barrier Breach Permits following previous changes to this process.
Several Shift Supervisors interviewed were unaware of their responsibility to initiate hourly fire watch patrols.
NRC Fenn 308A (649)
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Fort Calhoun Station Unit No. 1 0 Is lo j o j o l 21815 91 0 Ol0l1 01 0 01 3 oF 0l3 l
TEXT ta nuwe anses 4 soeused use seutuvieuv4C #eme m W (17)
As a result of previously identified deficiencies in the Fire Protection i
Program, Standing Order G-58 had been extensively revised and training of personnel prior to implementation of the revised procedure was in progress at the time of this event.
If implemented, the changes in G-58 would have prevented this event.
- - There was minimal safety significance associated with this event.
The area on the Room 26 side of the fire barrier is a short hallway with two closed doors (one door not fire rated) containing little or no flammable materials. The breach was a small hole drilled for conduit. Hence, the likelihood of a fire s
igniting in, spreading through, or spreading to this area from the Room 34 side of the barrier was minimal.
Fire detection instrumentation was operable in this area throughout this period. The area was without an hourly fire watch patrol for approximately 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.
Corrective actions associated with this event are:
(1)
Standing Order G-58 has been revised to require the Fire Protection System Engineer to coordinate planned system impairments.
The System Engineer will assign appro Technical Specifications. priate compensatory measures as required by The Shift Supervisor will assure compensatory measures are in place prior to approving system i
l impairments. Training on changes to G-58 will be completed for Shift Supervisors and other licensed operators prior to implenientation. The revised G-58 will be implemented by February 16, 1990 (2)
Operations Shift Supervisors have been reminded of their procedural L
resionsibility to verify that a fire watch is established before aut1orizing a fire barrier impairment.
(3)
Verbatim compliance and the total completion of all procedures and forms will continue to be stressed by management and Licensed Operator Requalification Training.
LER 88-030, LER 89-11, and LER 89-18 document previous events pertaining to failure to perform hourly fire watch patrols previously implemented. As noted above, corrective actions resulting from deficiencies associated with these events had not been fully implemented at the time of this latest event.
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05000285/LER-1990-001, :on 900108,fire Barrier for Wall Between Auxiliary Bldg Rooms 26 & 34 Breached But Hourly Fire Watch Patrol Not Established.Caused by Lack of Sufficient Training for Shift Supervisors.Standing Order Revised |
- on 900108,fire Barrier for Wall Between Auxiliary Bldg Rooms 26 & 34 Breached But Hourly Fire Watch Patrol Not Established.Caused by Lack of Sufficient Training for Shift Supervisors.Standing Order Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000285/LER-1990-002, :on 900226,inadvertent Actuation of Containment Isolation Actuation Signal Occurred W/Plant in Refueling Shutdown Condition.Caused by Accidental Actuation of Lockout Relay by Craftsman.Mod Procedure Revised |
- on 900226,inadvertent Actuation of Containment Isolation Actuation Signal Occurred W/Plant in Refueling Shutdown Condition.Caused by Accidental Actuation of Lockout Relay by Craftsman.Mod Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1990-003, :on 900216,determined That Auxiliary Feedwater Piping Outside Normal Stress Limits of ASME Code & Design Basis Specified in Updated Sar.Caused by Design Deficiency.Valve Operators Will Be Inspected |
- on 900216,determined That Auxiliary Feedwater Piping Outside Normal Stress Limits of ASME Code & Design Basis Specified in Updated Sar.Caused by Design Deficiency.Valve Operators Will Be Inspected
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2) | 05000285/LER-1990-004, :on 900217,lift Pressures for 6 of 10 Main Steam Safety Valves Found Outside Acceptance Criteria. Caused by Overly Restrictive Operability Criteria.Valves Recalibr & License Amend Submitted to NRC |
- on 900217,lift Pressures for 6 of 10 Main Steam Safety Valves Found Outside Acceptance Criteria. Caused by Overly Restrictive Operability Criteria.Valves Recalibr & License Amend Submitted to NRC
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1990-005, :on 900223,determined That Spent Fuel Pool Area Charcoal Filtration Unit VA-66 Was Outside Design Basis. Caused by Insufficient Airflow Into Unit.Affected Updated SAR Analysis Will Be Updated |
- on 900223,determined That Spent Fuel Pool Area Charcoal Filtration Unit VA-66 Was Outside Design Basis. Caused by Insufficient Airflow Into Unit.Affected Updated SAR Analysis Will Be Updated
| 10 CFR 50.73(a)(2) | 05000285/LER-1990-006, :on 900226,unplanned Actuation Occurred in Backup Trip Circuit for 345 Kv Breaker 3451-5.Probably Caused by Physical Disturbance & Resultant Actuation of Relay.Evaluation Will Be Performed |
- on 900226,unplanned Actuation Occurred in Backup Trip Circuit for 345 Kv Breaker 3451-5.Probably Caused by Physical Disturbance & Resultant Actuation of Relay.Evaluation Will Be Performed
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1990-007, :on 900228,determined That Several Supports Would Be Overloaded During Seismic Event on Nonsafety Related & safety-related Main Steam Piping.Caused by Design Deficiency.Piping Supports Modified |
- on 900228,determined That Several Supports Would Be Overloaded During Seismic Event on Nonsafety Related & safety-related Main Steam Piping.Caused by Design Deficiency.Piping Supports Modified
| | 05000285/LER-1990-008, :on 900306,electrician Was Connecting Leads as Part of Control Room Ventilation Mod & Caused Short Circuit While Working on Energized Circuit.Caused by Electrician Error.Enhanced General Guidelines Issued |
- on 900306,electrician Was Connecting Leads as Part of Control Room Ventilation Mod & Caused Short Circuit While Working on Energized Circuit.Caused by Electrician Error.Enhanced General Guidelines Issued
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1990-009, :on 900316,potential Overpressurization of Auxiliary Feedwater Piping Could Have Occurred During Thermal Expansion of Process Fluid Between Closed Valved. Caused by Design Deficiencies |
- on 900316,potential Overpressurization of Auxiliary Feedwater Piping Could Have Occurred During Thermal Expansion of Process Fluid Between Closed Valved. Caused by Design Deficiencies
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000285/LER-1990-010, :on 900327,unplan Attempt Start of Emergency Diesel Generator Occurred While Unit Was in Refueling Shutdown.Caused by Insufficient Guidance in Operating Instructions OI-DG-1 & OI-DG-2 |
- on 900327,unplan Attempt Start of Emergency Diesel Generator Occurred While Unit Was in Refueling Shutdown.Caused by Insufficient Guidance in Operating Instructions OI-DG-1 & OI-DG-2
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | 05000285/LER-1990-011, :on 900402,inadvertent Actuation of Pressurizer Pressure Low Signal Occurred While Performing Calibr Procedure.Caused by Inappropriate Action by Technician Involved.Validation of Procedures Reviewed |
- on 900402,inadvertent Actuation of Pressurizer Pressure Low Signal Occurred While Performing Calibr Procedure.Caused by Inappropriate Action by Technician Involved.Validation of Procedures Reviewed
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1990-014, :on 900427,investigation Revealed That Component Cooling Water Piping to Reactor Coolant Pump Seal Coolers Could Be Targets of High Energy Line Break.Safety Analysis for Operability Completed |
- on 900427,investigation Revealed That Component Cooling Water Piping to Reactor Coolant Pump Seal Coolers Could Be Targets of High Energy Line Break.Safety Analysis for Operability Completed
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1990-015, :on 900507,PORV Variable Setpoints Used for Low Pressure Overpressure Protection Determined to Be Nonconservative for PORV Opening Time.Caused by Design Deficiency.Tech Spec Amend Prepared |
- on 900507,PORV Variable Setpoints Used for Low Pressure Overpressure Protection Determined to Be Nonconservative for PORV Opening Time.Caused by Design Deficiency.Tech Spec Amend Prepared
| | 05000285/LER-1990-016, :on 900511,accident Scenarios Identified by Which Auxiliary Feedwater Piping from Discharge of Turbine Driven Auxiliary Feedwater Pump FW-10 Can Be Overpressurized.Caused by Design Deficiency |
- on 900511,accident Scenarios Identified by Which Auxiliary Feedwater Piping from Discharge of Turbine Driven Auxiliary Feedwater Pump FW-10 Can Be Overpressurized.Caused by Design Deficiency
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1990-018, :on 900612,reactor Protective Sys (RPS) Trip Units for Axial Power Distribution Determined to Be Inoperable.Caused by Procedural Deficiencies.Procedure Revised & RPS Surveillance Tests Reviewed |
- on 900612,reactor Protective Sys (RPS) Trip Units for Axial Power Distribution Determined to Be Inoperable.Caused by Procedural Deficiencies.Procedure Revised & RPS Surveillance Tests Reviewed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000285/LER-1990-021, :on 900829,inadvertent Reactor Protective Sys Actuation Occurred While Operator Changed Power Source. Caused by Operator Not Following Proper Procedures.Operator Counseled |
- on 900829,inadvertent Reactor Protective Sys Actuation Occurred While Operator Changed Power Source. Caused by Operator Not Following Proper Procedures.Operator Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1990-022, :on 900907,approx 460 Fire Barrier Penetration seals,60 Fire Dampers & 6 Fire Doors Declared Nonfunctional Per NRC Info Notice 88-004 Due to Lack of Documentation. Plant Outage Required to Implement Repairs/Replacements |
- on 900907,approx 460 Fire Barrier Penetration seals,60 Fire Dampers & 6 Fire Doors Declared Nonfunctional Per NRC Info Notice 88-004 Due to Lack of Documentation. Plant Outage Required to Implement Repairs/Replacements
| | 05000285/LER-1990-022-02, Forwards LER 90-022-02,providing Updated Total Numbers of Fire Barrier Impairments | Forwards LER 90-022-02,providing Updated Total Numbers of Fire Barrier Impairments | | 05000285/LER-1990-023, :on 900921,safety Injection Piping & Relief Valves Were Out of Design Basis |
- on 900921,safety Injection Piping & Relief Valves Were Out of Design Basis
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1990-024, :on 901026,discovered Failure to Conduct Hourly Firewatch |
- on 901026,discovered Failure to Conduct Hourly Firewatch
| 10 CFR 50.73(a)(2)(1) | 05000285/LER-1990-025, :on 900929,determined That Cooling Water Sys Outside Design Basis for post-accident Containment Cooling |
- on 900929,determined That Cooling Water Sys Outside Design Basis for post-accident Containment Cooling
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1990-026, :on 901119,pipe Joint at Isolation Valve in Turbine Bldg Instrument Air Header Failed,Resulting in Loss of Instrument Air Pressure & Reactor Trip.Caused by Improper Valve Installation.Joint Repaired |
- on 901119,pipe Joint at Isolation Valve in Turbine Bldg Instrument Air Header Failed,Resulting in Loss of Instrument Air Pressure & Reactor Trip.Caused by Improper Valve Installation.Joint Repaired
| | 05000285/LER-1990-027, :on 901207,determined That Adequate Compensatory Fire Watch Insp of Door 971-1 in Room 23 Not Conducted & 3 Addl Doors Had step-off Pads Outside Doors. Remedial Training Conducted |
- on 901207,determined That Adequate Compensatory Fire Watch Insp of Door 971-1 in Room 23 Not Conducted & 3 Addl Doors Had step-off Pads Outside Doors. Remedial Training Conducted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000285/LER-1990-028, :on 901214,investigation of Unknown RCS Leakage Identified Source as Installed Spare Control Element Drive Mechanism Housing 9.Caused by Lack of Venting Which Caused Igscc.Blank Flanges Installed |
- on 901214,investigation of Unknown RCS Leakage Identified Source as Installed Spare Control Element Drive Mechanism Housing 9.Caused by Lack of Venting Which Caused Igscc.Blank Flanges Installed
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